BSEP 06-0037, Notification of Deviation from Boiling Water Reactor Vessel and Internals Project Guidelines

Notification of Deviation from Boiling Water Reactor Vessel and Internals Project Guidelines

ML061090037
Person / Time
Site:	Brunswick
Issue date:	04/12/2006
From:	Ivey R Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 06-0037
Download: ML061090037 (4)

Text

Progress Energy APR 1 2 2006 SERIAL: B'SEP 06-0037 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 1 Docket No. 50-325/License No. DPR-71 Notification of Deviation From Boiling Water Reactor Vessel and Internals Project Guidelines Ladies and Gentlemen:

In accordance with BWR Vessel and Internals Project (BWRVIP) Report BWRVIP-94, Revision 1, BWR Vessel and InternalsProject, ProgramImplenmentation Guide, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., is notifying the NRC of deviations from BWRVIP guidelines taken by the Brunswick Steam Electric Plant, Unit No. 1. These deviations are associated with the repair of an indication on Core Spray System header piping weld P3c-270. The enclosure of this letter describes each deviation taken from BWRVIP guidelines and what is being done in lieu of the BWRVIP requirement. This information is being submitted to the NRC in accordance with Section 3.5, Reporting, of BWRVIP-94, Revision 1, and no NRC action is being requested in response to the submittal of this information.

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor - Licensing/Regulatory Programs, at (910) 457-2842.

Sincerely, C oet Randy C. Ivey Manager - Support Services Brunswick Steam Electric Plant WRM/wrm

Enclosure:

Descriptions of Deviations From Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guideline Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant P.O.Box 10429 Southport, NC 28461 C)D

Document Control Desk BSEP 06-0037 / Page 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region 11 ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Ids. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Ms. Meena Khanna (Mail Stop OWFN 9H4) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission AlTTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

Enclosure BSEP 06-0037 Page 1 of 2 Descriptions of Deviations From Boiling Water Reactor Vessel and Internals Proiect (BWRVIP) Guideline In accordance with BWR Vessel and Internals Project (BWRVIP) Report BWRVIP-94, Revision 1, BIAR Vessel and InternalsProject, ProgramImplementation Guide, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., is notifying the NRC of deviations from BWRVIP guidelines taken by the Brunswick Steam Electric Plant (BSEP), Unit No. 1. These deviations are associated with the repair of an indication on Core Spray System header piping weld P3c-270.

BWRVIP-94, Revision 1, provides implementation guidance to ensure the consistent application of 13WRVIP guidelines by BWRVIP member utilities. Section 3.5 of BWRVIP-94, Revision 1, provides specific guidance for the reporting of inspection results, new repairs, and deviations taken from BWRVIP guidelines. If a utility does not implement any portion of an applicable "mandatory" or "needed" BWRVIP guideline that has been approved by the BWRVIP Executive Committee and transmitted to the NRC, the utility is required to notify the NRC and BWRVIP within 45 days following the utility executive concurrence with the disposition of the deviation. The utility is required to describe what 13WRVIP requirement they are deviating from and what is being done in lieu of the applicable requirement.

During the BSEEP Unit 1 refueling outage, which began on March 4, 2006, CP&L performed inspections of Core Spray System piping and spargers in accordance with BWRVIP-1 8-A, BWR Vessel and Internals Project, BWR Core Spray InternalsInspection and Flaw Evaluation Guidelines. These inspections identified an indication on the B loop Core Spray System piping inside the reactor pressure vessel which required repair. BWRVIP-19-A, BWR Vessel and Internals Project, Internal Core Spray Piping and SpargerRepairDesign Criteria,was used for the design, fabrication, and installation of the piping clamp used as a repair. For this repair, the following deviations were taken from the applicable BWRVLP guidelines, as described below.

Enclosure BSEP 06-0037 Page 2 of 2 BWRVIP Alternative Document BWRVIP Requirement Exception In Lieu Of BWRVIP-84, Bending Process - Solution annealing The locking pins and Section A.9.3.1 Components formed by after peening of crimp cups have been bending shall be fully locking pins (i.e., a machined from SA-479, solution annealed after fabrication operation) Type 316L stainless steel the bending process. and crimping of the barstock with low carbon crimp cups (i.e., an content.

underwater installation The function of the operation) will not be crimp cup is to prevent performed. loosening of the bolt.

Some plastic deformation was required during the installation process.

Each crimp cup has been pinned to the pipe assembly and the shear pins have been retained in place by locking pins.

Repair clamp inspections will be performed using VT-1IVT-3 techniques and controlled through plant procedures.

Initially, the repair clamp will be inspected each refueling outage. The frequency for future repair clamp re-inspections may be extended based on inspection performance.

BWRVIP-84, Packaging, shipping, ANSI 45.2.2 for ANSI 45.2.2 has been Section A. 1 and storage shall be in packaging, storage, supplemented with accordance with ASME and handling will be additional requirements NQA-2-1989, Part 2.2, used in lieu of ASME in order to meet criteria, Level B for welding NQA-2. equivalent to ASME filler materials, and NQA-2-1989, Part 2.2, Level C for all other Level C.

materials.